The present invention relates to a process of removing free-unlabeled radionuclides from a radiopharmaceutical prior to administering the radiopharmaceutical to the patient using size-exclusion or ion-exchange mechanisms.

Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

Disclosed are methods and systems for hydrogen isotope exchange of organic molecules that can be carried out with no alteration in the chemical structure of the organic molecules. Methods can be utilized to incorporate a particular hydrogen isotope on an organic molecule (e.g., deuteration or tritiation) or to remove a particular hydrogen isotope from an organic molecule (e.g., detritiation).

The present invention relates to a method of producing and refining carrier-free lutetium-177 using chromatography, and more specifically to a method of producing and refining carrier-free lutetium 1-77 using chromatography having excellent resolution of lutetium and ytterbium without a concentration gradient of an eluent.

A system, apparatus and process for separating a tritiated heavy water stream into a tritium-lean heavy water stream and a tritium-enriched heavy water stream. Tritiated heavy water (DTO/D2O) is fed to a mid-point of an isotope exchange column. The column contains a hydrophobic solid catalyst to promote exchange of deuterium and tritium. DT/D2 gas flows out of an electrolysis cell and into the first end of the column, concentrating tritium content in the heavy water by counter current flow to produce a tritium-rich heavy water below the feed point and a tritium-lean deuterium gas above. Tritium-rich heavy water flows out the first end of the column and into the electrolysis cell, forming DT/D2 gas and a tritium-enriched heavy water stream. Tritium-lean deuterium gas flows out the second end of the column and into a tritium-lean heavy water unit. Either O2 gas or light water additionally flows into the tritium-lean heavy water unit to form a tritium-lean heavy water.

Submersible media filters and submersible columns for use in removing radioactive isotopes and other contaminants from a fluid stream, such as a fluid stream from the primary coolant loop of a nuclear reactor system or a fluid stream from a spent-fuel pool. Generally, these submersible media filters and submersible columns are adapted to be submersed in the fluid stream, and additionally the filters are adapted to be vitrified after use, resulting in a stabilized, non-leaching final waste product with a substantially reduced volume compared to the original filter. In several embodiments, the submersible media filters and submersible columns include isotope-specific media (ISM).

Submersible media filters and submersible columns for use in removing radioactive isotopes and other contaminants from a fluid stream, such as a fluid stream from the primary coolant loop of a nuclear reactor system or a fluid stream from a spent-fuel pool. Generally, these submersible media filters and submersible columns are adapted to be submersed in the fluid stream, and additionally the filters are adapted to be vitrified after use, resulting in a stabilized, non-leaching final waste product with a substantially reduced volume compared to the original filter. In several embodiments, the submersible media filters and submersible columns include isotope-specific media (ISM).